US3185631A - Assembly comprising a heat source and associated apparatus - Google Patents

Assembly comprising a heat source and associated apparatus Download PDF

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Publication number
US3185631A
US3185631A US832960A US83296059A US3185631A US 3185631 A US3185631 A US 3185631A US 832960 A US832960 A US 832960A US 83296059 A US83296059 A US 83296059A US 3185631 A US3185631 A US 3185631A
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United States
Prior art keywords
pressure vessel
heat
heat exchanger
coolant
heat source
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Expired - Lifetime
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US832960A
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English (en)
Inventor
Long Everett
Rodwell William
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UK Atomic Energy Authority
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UK Atomic Energy Authority
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/10—Means for supporting the complete structure
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/024—Supporting constructions for pressure vessels or containment vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/04—Arrangements for expansion and contraction
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This invention relates to that kind of assembly which comprises a massive heat source, for example, a nuclear reactor, and massive apparatus, for example one or more heat exchangers, connected thereto, wherein temperature changes occur in the heat source and give rise to problems of thermal expansion.
  • a massive heat source for example, a nuclear reactor
  • massive apparatus for example one or more heat exchangers
  • a nuclear reactor has been provided with a closed system coolant circuit having an inlet duct to the reactor pressure vessel, the vessel being secured to the ground, a separate outlet duct, a heat exchanger, also secured to the ground, in circuit with the inlet and outlet ducts, and means for efiecting flow of coolant in the said circuit.
  • the temperature difference between the cooler inlet duct and the hot outlet duct gave rise to thermal expansion difiiculties which could only be overcome by providing expansion joints in each duct so that the unequal expansion of the ducts could be accommodated without serious stressing of the ducts, heat exchanger and pressure vessel.
  • Another disadvantage of the use of separate ducts lies in the fact that the duct containing the hot fluid needs to be either of heat resistant material or lined internally with heat insulating material and cooled externally.
  • the first alternative gives rise to serious difiiculty in efiecting a secure joint between the duct and the pressure vessel.
  • the second alternative has an element of risk in that mechanical failure of even a small area of insulation gives rise to a local hot spot and the probability of a disastrous breach of the coolant circuit.
  • an assembly of the hereinbetore specified kind has means for peripherally supporting the heat source so as to allow of expansion and contraction movement, occurring on temperature change, radially relative to an immovable axis of the heat source, means for supporting said massive apparatus so that the latter is capable of moving as dictated by the expansion or contraction of the heat source, by the expansion or contraction of the means connecting the heat source to the apparatus, and by its own expansion or contraction, and the heat source and apparatus being supported in a plane which is common to both, is at right angles to the said axis and furthermore contains the axis of the con necting means, said connecting means being coaxial ducting providing two-way connection between the heat source and the said apparatus.
  • the inner duct is preferably the outflow from the heat source.
  • Valve means is preferably provided for both inner and outer ducts.
  • the said means for supporting the heat source preferably comprises supporting structures disposed peripherally around the heat source, projections of the heat source being mounted on rollers supported by the said structures with their axes generally at right angles to radial relative to the axis of the heat source.
  • rollers balls or differential roller assemblies may be used.
  • Means for supporting the said apparatus may be similar to the means for supporting the heat source, except that the axes of the rollers are all generally at right angles to a line intersecting the respective roller and passing through the axis of the heat source.
  • rollers balls or diflferential roller assemblies may be used.
  • FIGURE 1 is a fragmentary side view, regarded in the direction of arrow I of FIGURE 2, of an assembly according to the invention
  • FIGURE 2 is a plan view in section on a line corresponding to line IIII of FIGURE 1,
  • FIGURE 3 is a detached side view in section of means for supporting the heat source, drawn to a larger scale than FIGURES 1 and 2,
  • FIGURE 4 is a similar view to FIGURE 3 and illustrates an alternative construction of supporting means as applied to the apparatus connected to the heat source,
  • FIGURE 5 is a diagrammatic side view in medial section of an alternative supporting expedient
  • FIGURE 6 is a side view in medial section of an assembly of particular application.
  • FIGURE 7 is a plan View in section on line VI-IVII of FIGURE 6.
  • FIGURES 1-4 in the construction shown in FIGURES 1-4 thereof, as applied by way of example to an assembly consisting of a massive heat source connected to one or more massive heat exchangers, we provide a generally cylindrical-walled massive heat source 1 provided with a plurality, for example, as shown in FIGURE 2, eight peripherally spaced lugs 2 having strengthening fillets or ribs 3. Pillars 4 provided on an annular supporting ledge 5 each have a member 6 (see particularly FIGURE 3) supporting rollers 7 carrying the respective lug 2 through interposition of a member 8 having an arcuate upper surface engaging the lug 2. In order to eifect load-balancing, a member 9 of corrugated preferably resilient plate metal is interposed between the pillars 4i and the respective members 6.
  • the axes of the rollers 7 are at right angles to a radial line A (see FIG- URE 2) from the axis of the heat source (indicated by the dot-and-dash lines 10 in FIGURE 1 and by the point lil in FIGURE 2) which bisects the respective roller 7.
  • the heat source 1 is connected to one or more heat exchangers 11 (two of which are shown. in FIGURE 2 by way of example, connections for a further two heat exchangers being also shown) by coaxial ducting 12 providing an inner duct 13 conveying fluid heat transfer medium (arrow 13a) from the heat source 1 to the heat exchanger 11 or respective heat exchanger, and an outer duct 14 returning the said fluid (arrow 14b) to the heat source I.
  • the common axis of the ducting 12 is in the same plane (indicated by line B of FIGURE 1) as the plane of support of the heat source 1, which latter is the plane containing the lower surfaces of the members 8.
  • Each heat exchanger 11 is generally cylindrical-walled and has peripherally spaced lugs (four of which are shown per heat exchanged by way of example in FIG- URE 2) with fillets or ribs 16, similar to the lugs 2 and ribs 3 of the heat source 1, supported through the intermediary of members 17, similar to the members 8, upon rollers 18 which are themselves supported by pillars 19 carried by an annular supporting ledge (which may be integral with the ledge 5) through the intermediary of load-balancing members 21 and 22 (see FIGURE 4).
  • the expedient illustrated in FIGURE 3 may be employed for load-balancing of each heat ex- I changer 11, namely substitution of members 6 and 9 of FIGURE 3 for members 21 and 22 respectively, of FIG- URE 4.
  • each heat exchanger 11 namely the plane containing the lower surfaces of the members 17 (line B of FIGURE 1), contains the com- 2 mon axis of the ducting 11, land the axis of each roller 18 is at right angles to a radial line (for example line C of FIGURE 2), from the 'axis of the heat source 1 which bisects the respective roller 18.
  • a radial line for example line C of FIGURE 2
  • the alignment of the axes of the rollers 7 is such as to allow of expansion of the heat source radially outwardly from its axis 10
  • the alignment of the axes of the rollers 18 is such as to allow of the radial expansion of the heat source and the corresponding bodily movement of each heat exchanger 11 together with the radial expansion of each heat exchanger 11 itself.
  • balls may be employed instead of employing rollers 7 for supporting the heat source.
  • This alternative is illustrated in FIG- URE 2 wherein balls :are shown in dot-and-dash lines and designated 35.
  • Balls may also be employed for supporting the or each heat exchanger 11 instead of the rollers 18, being shown by way of example in FIGURE 2 in dot-
  • dilferential roller assemblies may be employed.
  • a suitable assembly is illustrated diagrammatically in FIGURE 5 and consists of a series of rollers 37, a series of rollers 38, and a floating plate 39 separating the two series, the parallel axes of the rollers of one series being at right angles to those of the other series.
  • Each assembly may replace the rollers 7 or balls supporting the heat source 1, or the rollers 18 or balls 36 supporting each heat exchanger 11.
  • the advantage of employing the balls or dilferential roller assemblies is that they allow for differential expansion or contraction as may occur, for example, if one or more of the heat exchangers 11 be isolated from the heat source 1 with the remainder in connection.
  • FIGURES 6 and 7 the application of the invention to a nuclear reactor as heat source is illustrated, the construction'being similar in principle to that described with reference to FIGURES l to 5.
  • a nuclear reactor core structure 23 forms the heat source and is confined in a pressure vessel 24 which has lugs 25 with strengthening fillets or ribs 26 and is supported in a similar manner to that described with reference to FIGURES 1, 2 and 3 or 5 by rollers, balls or differential roller assemblies as he-reinbefore described, engaging, through load-balancing devices, pillars (not shown) extending from an annular ledge 27 formed as part of the containment 28 which is usually of reinforced concrete.
  • Co-axial ducting 29 having an outlet duct 29a and an inlet duct 2% and having poppet valves for the outer ducting and butterfly valves 41 for the inner ducting connects the pressure vessel 24 with four heat exchangers 30 disposed within the containment 23 and supported by means of lugs 31 having stiffening fillets or ribs 32, rollers (or balls of difi-erential roller assemblies), load balancing devices and pillars (not shown), the pillars being carried on an annular ledge 33 of the containment 28, in similar manner to that described for the heat exchanger(s) 11 with reference to FIGURES 1, 2 and 4 or 5.
  • the planes of support of the pressure vessel 24 and heat exchangers 30 and the axis of the ducting 29 lie in a common plane illustrated by the line D of FIGURE 5.
  • Gaseous coolant is circulated between reactor core 23 and heat exchangers 30 by a cir-culator 34 disposed within the body of each heat exchanger 30.
  • the coolant is circulated along the outer ducts 29a into the pressure vessel 24 where it passes downwardly (arrow 29g) in contact with the cylindrical wall thereof, upwardly (arrow 290) over fuel elements in the core of the reactor, into a hot box 29d within the pressure vessel, along the inner duct-s 2912 which are connected to the hot box through expansion joints (arrow 29 upwardly through the heat removing means of the heat exchanger 30, and downwardly in contact with the cylindrical walls of the heat exchangers 30 to the respective circulate-rs 34.
  • the poppet valves 40 and butterfly valve-s 41 may be, for example, as disclosed in British Patent specification No. 886,320 and serve for isolating the heat exchangers 30 separately or collectively from the pressure vessel 24.
  • the inner ducts are provided with internal lagging to minimise heat loss to the outer ducts.
  • the advantage of employing co-axial ducting resides mainly in its greater safety but also resides in its resolving of the mechanical problems presented by employing separate ducts.
  • the hot fluid inner duct of the oo-axial ducting has to support only a small pressure diflerence. Since the higher pressure is on the outside, failure of the heat insulation lagging and subsequent rupture would lead to an inward leak of '0001 gas and the integrity of the main pressure bearing membranes would not be jeopardized.
  • load bearing by the reactor pressure vessel is improved by the means of support thereof.
  • a reactor pressure vessel is supported at or near its base by a skirt
  • stressing of the vesscl due to the weight of its shell and the weight of components connected thereto above the skirt support, such as ducting, access standpipes, etc. is manifest as a compressive loading tending to radial distortion of the vessel.
  • the vessel in the region of the supports is subjected to a tensile loading due to the weight of the part of the vessel below the supports.
  • This loading is increased by the weight of components within the pressure vessel, such as the moderator, reflector, fuel elements, and an internal neutron shield (see for example our copending US. application Serial No. 798,59) which can either be suspended in a cradle from that part of the vessel which carries the supports or can be mounted on a grid structure carried by brackets on the interior bottom part of the vessel.
  • the vessel can be constructed to accept such tensile loading, tor example 'by increasing plate thickness in the region of the supports where suspension of the internal load is employed, and the greater part oi the vessel is then not subject to radial distortion.
  • the vessel in the region of the supports is then only subjected to a compressive loading due to the weight of the top dome of the vessel and the Weight of access standpipe-s passing therethrough, and as this loading will be small compared with the tensile loading, it can easily be designed for, as by increasing the thickness of the vessel in the said region, so that no radial distortion of the pressure vessel occurs.
  • a nuclear reactor having a reactor core, a pressure vessel containing the core, a coolant circulator to circulate coolant through the vessel to extract heat from the core, a heat exchanger to which the coolant yields its heat, coaxial ducting extending between the pressure vessel and the heat exchanger for the transfer of coolant etween them, and bearings for the pressure vessel and heat exchanger supporting the pressure vessel and heat exchanger for movement radially with respect to each other, said bearings lying in the same plane as the axis of the coaxial ducting.
  • a nuclear reactor having a reactor core, a pressure vessel containing the core, a coolant circulator to circulate coolant through the vessel to extract heat from the core, heat exchangers to which the coolant yields its heat, coaxial ducts extending radially of the pressure vessel for the transfer of coolant to heat exchangers disposed around the pressure vessel, and bearings for the pressure vessel and heat exchangers supporting the pressure vessel and heat exchanger for movement radially with respect to each other, said bearings lying in the same plane as the axis of the coaxial ducts.
  • a pressure vessel containing the core a coolant circulator to circuluate coolant through the vessel to extract heat from the core, heat exchangers to which the coolant yields its heat, straight coaxial ducts extending between the pressure vessel and the heat exchan ers in a direction radial to both the pressure vessel and their respective heat exchangers for the transfer of coolant between them, and bearings for the pressure vessel and heat exchangers supporting the pressure vessel and heat exchanger for movement radially with respect to each other, said bearings lying in the same plane as the axes of the coaxial ducts.
  • a pres sure vessel containing the core a coolant circulator to circulate coolant through the vessel to extract heat from the core, heat exchangers to which the coolant yields its heat, coaxial ducts extending radially of the pressure vessel for the transfer of coolant to heat exchangers disposed around the pressure vessel, roller bearings for the pres sure vessel which lie in the same plane as the coaxial ducts and have their axes so aligned that they permit radial thermal expansion and contraction of the pressure vessel while restricting lateral movements of the pressure vessel, and roller bearings for the heat exchangers which lie in the same plane as the coaxial ducts and have their axes so aligned that they permit thermal movement of the heat exchangers in a direction radial to the pressure vessel while restricting lateral movement of the heat exchangers.
  • a pressurized fluid-cooled nuclear reactor system comprising a reactor pressure vessel, a. reactor core in said pressure vessel, a heat exchanger, straight horizontal coaxial ducts between said reactor pressure vessel and heat exchanger, rolling support means for the pressure vessel disposed to allow radial expansion of the pressure vessel in the horizontal plane of said ducts, rolling sup port means for the heat exchanger also in said horizontal plane disposed to allow movement of the heat exchanger colinearly with said ducts and reactor coolant circulating means appended to said heat exchanger.
  • a pressurized fluid-cooled nuclear reactor system comprising a reactor pressure vessel, a reactor core in said pressure vessel, means defining coolant flow from an upper level in said vessel over the wall of said vessel and thence upwards through channels in said core, a coolant collecting box above said core having connections with said channels, a duct from said.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
US832960A 1958-08-11 1959-08-11 Assembly comprising a heat source and associated apparatus Expired - Lifetime US3185631A (en)

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GB25799/58A GB897445A (en) 1958-08-11 1958-08-11 Improvements in or relating to an assembly comprising a heat source and associated apparatus

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CH (1) CH378428A (fi)
FR (1) FR1232143A (fi)
GB (2) GB897445A (fi)
NL (2) NL121725C (fi)

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3367839A (en) * 1964-07-17 1968-02-06 Fiat Spa Closed cycle nuclear reactor
US3395076A (en) * 1966-02-23 1968-07-30 Westinghouse Electric Corp Compact nuclear reactor heat exchanging system
US3425907A (en) * 1965-09-20 1969-02-04 Reactor Centrum Nederland Nuclear energy reactor plant having one or more heat exchangers
US3716451A (en) * 1970-11-30 1973-02-13 Stone & Webster Eng Corp Nuclear reactor power plant structural support system
US3897838A (en) * 1969-08-06 1975-08-05 Atomic Energy Authority Uk Nuclear reactor power plant
EP0006801A1 (fr) * 1978-06-23 1980-01-09 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Chaudière nucléaire à neutrons rapides à métal liquide caloporteur
FR2434461A1 (fr) * 1978-06-23 1980-03-21 Bretagne Atel Chantiers Nouveau dispositif de supportage et de protection pour chaudieres nucleaires
US4219385A (en) * 1977-06-17 1980-08-26 Commissariat A L'energie Atomique Circulating pumps of a liquid metal, generally sodium, ensuring the cooling of the core of a fast neutron reactor
US4280871A (en) * 1974-01-25 1981-07-28 Kraftwerk Union Aktiengesellschaft Live steam shut-off device for pressurized water reactors
FR2538156A1 (fr) * 1982-12-17 1984-06-22 Commissariat Energie Atomique Circuit de refroidissement d'un reacteur nucleaire refroidi par un metal liquide
US4796695A (en) * 1983-06-30 1989-01-10 Phillips Petroleum Company Tube supports
WO2020239441A1 (en) * 2019-05-24 2020-12-03 Rolls-Royce Plc A pressure-containing silo for a pressurised water reactor nuclear power plant

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3192121A (en) * 1958-08-11 1965-06-29 Atomic Energy Authority Uk Nuclear reactor systems
GB1146327A (en) * 1965-06-18 1969-03-26 English Electric Co Ltd Nuclear reactors
DE2101965B2 (de) * 1971-01-16 1972-05-25 Siemens AG, 1000 Berlin u. 8000 München Vorrichtung zur aufhaengung und abstuetzung von reaktordruckbehaeltern in atomkernkraftwerken
GB1567039A (en) * 1976-08-12 1980-05-08 Nuclear Power Co Ltd Liquid metal cooled nuclear reactor constructions
US4115194A (en) * 1977-02-22 1978-09-19 The Babcock & Wilcox Company Reactor pressure vessel support
AT380913B (de) * 1983-10-06 1986-07-25 Voest Alpine Ag Montageabstuetzung zum einsetzen der unteren kalotte eines metallischen kugelbehaelters in ein betonbett

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2115714A (en) * 1935-02-26 1938-05-03 Houdry Process Corp Heat exchange apparatus
US2712426A (en) * 1954-04-22 1955-07-05 Sun Oil Co Reactor supports
GB785528A (en) * 1956-02-29 1957-10-30 Asea Ab Nuclear reactor plant
GB789022A (en) * 1955-06-10 1958-01-15 Gen Electric Co Ltd Improvements in or relating to nuclear reactors
US2838451A (en) * 1954-11-13 1958-06-10 Long Everett Gas cooled nuclear reactors
US2863815A (en) * 1953-07-23 1958-12-09 Moore Richard Valentine Nuclear reactor
US7810689B2 (en) * 2005-05-25 2010-10-12 Sebek Limited Stapler

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2115714A (en) * 1935-02-26 1938-05-03 Houdry Process Corp Heat exchange apparatus
US2863815A (en) * 1953-07-23 1958-12-09 Moore Richard Valentine Nuclear reactor
US2712426A (en) * 1954-04-22 1955-07-05 Sun Oil Co Reactor supports
US2838451A (en) * 1954-11-13 1958-06-10 Long Everett Gas cooled nuclear reactors
GB789022A (en) * 1955-06-10 1958-01-15 Gen Electric Co Ltd Improvements in or relating to nuclear reactors
GB785528A (en) * 1956-02-29 1957-10-30 Asea Ab Nuclear reactor plant
US7810689B2 (en) * 2005-05-25 2010-10-12 Sebek Limited Stapler

Cited By (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3367839A (en) * 1964-07-17 1968-02-06 Fiat Spa Closed cycle nuclear reactor
US3425907A (en) * 1965-09-20 1969-02-04 Reactor Centrum Nederland Nuclear energy reactor plant having one or more heat exchangers
US3395076A (en) * 1966-02-23 1968-07-30 Westinghouse Electric Corp Compact nuclear reactor heat exchanging system
US3897838A (en) * 1969-08-06 1975-08-05 Atomic Energy Authority Uk Nuclear reactor power plant
US3716451A (en) * 1970-11-30 1973-02-13 Stone & Webster Eng Corp Nuclear reactor power plant structural support system
US4280871A (en) * 1974-01-25 1981-07-28 Kraftwerk Union Aktiengesellschaft Live steam shut-off device for pressurized water reactors
US4219385A (en) * 1977-06-17 1980-08-26 Commissariat A L'energie Atomique Circulating pumps of a liquid metal, generally sodium, ensuring the cooling of the core of a fast neutron reactor
EP0012042A1 (fr) * 1978-06-23 1980-06-11 ATELIERS ET CHANTIERS DE BRETAGNE ACB Société anonyme dite: Dispositif de supportage et de protection pour chaudières nucléaires
FR2434461A1 (fr) * 1978-06-23 1980-03-21 Bretagne Atel Chantiers Nouveau dispositif de supportage et de protection pour chaudieres nucleaires
FR2429477A1 (fr) * 1978-06-23 1980-01-18 Commissariat Energie Atomique Chaudiere nucleaire a neutrons rapides a metal liquide caloporteur
EP0006801A1 (fr) * 1978-06-23 1980-01-09 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Chaudière nucléaire à neutrons rapides à métal liquide caloporteur
US4335467A (en) * 1978-06-23 1982-06-15 Commissariat A L'energie Atomique Liquid metal cooled nuclear reactor
US4511532A (en) * 1978-06-23 1985-04-16 Ateliers Et Chantiers De Bretagne, A C B Device for supporting and protecting nuclear boilers
FR2538156A1 (fr) * 1982-12-17 1984-06-22 Commissariat Energie Atomique Circuit de refroidissement d'un reacteur nucleaire refroidi par un metal liquide
EP0114545A1 (fr) * 1982-12-17 1984-08-01 Commissariat A L'energie Atomique Circuit de refroidissement d'un réacteur nucléaire refroidi par un métal liquide
US4796695A (en) * 1983-06-30 1989-01-10 Phillips Petroleum Company Tube supports
WO2020239441A1 (en) * 2019-05-24 2020-12-03 Rolls-Royce Plc A pressure-containing silo for a pressurised water reactor nuclear power plant

Also Published As

Publication number Publication date
CH378428A (de) 1964-06-15
NL121725C (fi)
GB983742A (en) 1965-02-17
GB897445A (en) 1962-05-30
NL242128A (fi)
FR1232143A (fr) 1960-10-05

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